A carbon-carbon panel design concept for the inboard limiter of the Compact Ignition Tokamak (CIT)

Author

Mantz, H.C. ; Bowers, D.A. ; Williams, F.R. ; Witten, M.A.

Author_Institution

McDonnell Douglas Missile Syst. Co., St. Louis, MI, USA

fYear

1989

fDate

2-6 Oct 1989

Firstpage

947

Abstract

The limiter region of the Compact Ignition Tokamak (CIT) must withstand nominal heat fluxes in excess of 10 MW/m² in order to protect the vacuum vessel from the plasma energy, and it must be designed to be remotely maintained. Because of its ability to meet the thermal and structural requirements, carbon-carbon composite material was selected over bulk graphite materials for the limiter design. The structural design concept consists of carbon-carbon composite panels attached to the vacuum vessel by a hinged rod/retainer concept. Results of the preliminary design study to define this inboard limiter are presented. The design concept is described along with the analyses of the thermal and structural response during nominal plasma operation and during plasma disruption events

Keywords

Tokamak devices; composite materials; fusion reactor materials; fusion reactor theory and design; C-C composite panel; CIT; Compact Ignition Tokamak; design; inboard limiter; plasma disruption events; structural design concept; Composite materials; Elementary particle vacuum; Ignition; Organic materials; Plasma devices; Plasma materials processing; Plasma temperature; Power system protection; Tiles; Tokamaks;

fLanguage

English

Publisher

ieee

Conference_Titel

Fusion Engineering, 1989. Proceedings., IEEE Thirteenth Symposium on

Conference_Location

Knoxville, TN

Type

conf

DOI

10.1109/FUSION.1989.102373

Filename

102373